44-Ru-104 JAEA EVAL-JUL12 K.Shibata JNST 50, 1177 (2013) DIST-DEC21 20180517 ----JENDL-5 MATERIAL 4449 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 12-07 The fast neutron cross sections were re-evaluated by K.Shibata (JAEA) /1/ using the POD code. 18-05 Activation cross sections added by K.Shibata. 21-11 revised by O.Iwamoto (MF8/MT4) added 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved Resonance Region (MLBW; below 11.12 keV) Parameters for JENDL-2 were evaluated as follows: Resonance energies below 2 keV were taken from the experimental data by Priesmeyer and Jung/2/ and Shaw et al./3/, other resonances above 2.7 keV were determined from Macklin and Halperin/4/. The neutron widths were evaluated on the basis of the data of Priesmeyer and Jung, and of Macklin and Halperin. The radiation widths of large resonances were taken from Ref./4/ For the others, the average radiation width of 0.103+-0.018 eV was deduced, and adopted for the levels whose radiation width was unknown. Seven hypothetical resonances were generated in the energy range from 2 to 2.7 keV. For the levels observed by Shaw et al. and the hypothetical ones, reduced neutron widths of 12 and 38 meV were given for s-wave and p-wave resonances, respectively. A negative resonance was added at -941 eV so as to reproduce the capture cross section of 0.32+-0.02 barns at 0.0253 eV/5/. For JENDL-3, parameters of the first positive and negative resonances were modified so as to reproduce the resonance integral recommended by Mughabghab et al./5/ Scattering radius was reduced from 6.35 fm to 6.1 fm on the basis of the systematics. Resonance parameters of JENDL-3.3 were adopted for JENDL-4.0 by revising those of the negative resonance so that the thermal capture cross section was in good areement with experimental data of 0.47 b/6,7/. Scattering radius was changed from 6.35 fm to 6.5 fm considering its systematics/8/. Unresolved resonance region: 11.12 keV - 300 keV The parameters were obtained by fitting to the calculated total and capture cross sections. The unresolved resonance parameters obtained should be used only for self-shielding calculation. URP's were re-calculated by fitting to the total and capture cross sections calculated by POD /9/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 6.9313E+00 Elastic 6.4621E+00 n,gamma 4.6912E-01 6.5786E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /9/. MT= 2 Elastic scattering cross section The cross section was obtained by subtracting the non-elastic cross section from the total cross section. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT= 4,51-91 (n,n') cross section Calculated with POD code /9/. MT= 16 (n,2n) cross section Calculated with POD code /9/. MT= 17 (n,3n) cross section Calculated with POD code /9/. MT= 22 (n,na) cross section Calculated with POD code /9/. MT= 28 (n,np) cross section Calculated with POD code /9/. MT= 32 (n,nd) cross section Calculated with POD code /9/. MT=102 Capture cross section Calculated with POD code /9/. MT=103 (n,p) cross section Calculated with POD code /9/. MT=104 (n,d) cross section Calculated with POD code /9/. MT=105 (n,t) cross section Calculated with POD code /9/. MT=106 (n,He3) cross section Calculated with POD code /9/. MT=107 (n,a) cross section Calculated with POD code /9/. MT=203 (n,xp) cross section Calculated with POD code /9/. MT=204 (n,xd) cross section Calculated with POD code /9/. MT=205 (n,xt) cross section Calculated with POD code /9/. MT=206 (n,xHe3) cross section Calculated with POD code /9/. MT=207 (n,xa) cross section Calculated with POD code /9/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /9/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/9/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/9/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/9/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/9/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/9/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/9/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/9/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/9/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/9/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/9/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/9/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/9/. MF= 8 Information on decay data MT= 16 (n,2n) reaction MT= 17 (n,3n) reaction MT= 22 (n,na) reaction MT= 28 (n,np) reaction MT= 32 (n,nd) reaction MT=102 (n,g) reaction MT=103 (n,p) reaction MT=104 (n,d) reaction MT=105 (n,t) reaction MT=106 (n,He3) reaction MT=107 (n,a) reaction MF=10 Nuclide production cross sections MT= 32 Partial (n,nd) reactions Calculated with POD code /9/. MT=105 Partial (n,t) reactions Calculated with POD code /9/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /9/. MF=14 Gamma-ray angular distributions MT= 3 Non-elastic gamma emission Assumed to be isotropic. MF=15 Gamma-ray spectra MT= 3 Non-elastic gamma emission Calculated with POD code /9/. *************************************************************** * Nuclear Model Calculations with POD Code /9/ * *************************************************************** 1. Theoretical models The POD code is based on the spherical optical model, the distorted-wave Born approximaiton (DWBA), one-component exciton preequilibrium model, and the Hauser-Feshbach-Moldauer statis- tical model. With the preequilibrim model, semi-empirical pickup and knockout process can be taken into account for composite-particle emission. The gamma-ray emission from the compound nucleus can be calculated within the framework of the exciton model. The code is capable of reading in particle transmission coefficients calculated by separate spherical or coupled-channel optical model code. 2. Optical model parameters Neutrons: Coupled-channel optical model parameters /10/ Protons: Koning and Delaroche /11/ Deuterons: Lohr and Haeberli /12/ Tritons: Becchetti and Greenlees /13/ He-3: Becchetti and Greenlees /13/ Alphas: Lemos /14/ potentials modified by Arthur and Young /15/ 3. Level scheme of Ru-104 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1* 0.35802 2 + 2* 0.88848 4 + 3* 0.89310 2 + 4 0.98827 0 + 5 1.24236 3 + 6 1.33500 0 + 7 1.50260 4 + 8 1.51544 2 + 9 1.55640 6 + 10 1.75000 2 + 11 1.87239 5 + 12* 1.97043 3 - 13 1.97480 6 - 14 2.00400 2 + 15 2.03485 2 + 16 2.08084 4 + 17 2.09500 2 + 18 2.19660 6 + 19 2.23280 5 - 20 2.26904 3 + 21 2.28507 2 + 22 2.32040 8 + 23 2.32922 3 - 24 2.37375 1 + 25 2.42985 5 - 26 2.44300 2 + 27 2.48190 3 - 28 2.48991 2 + 29 2.52428 2 + 30 2.59731 2 - 31 2.60070 6 - 32 2.61390 7 - 33 2.61897 2 + ------------------------- Levels above 2.62897 MeV are assumed to be continuous. The symbol (*) stands for the excited level involved in the coupled-channel calculation. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /16/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Ru-105 14.068 1.171 4.250 0.657 -1.412 7.205 0.914 Ru-104 13.272 2.353 3.632 0.656 0.316 7.723 2.619 Ru-103 13.854 1.182 3.548 0.717 -1.842 8.034 0.954 Ru-102 13.056 2.376 2.653 0.711 0.144 8.244 2.460 Tc-104 13.220 0.000 4.817 0.571 -1.464 4.245 0.399 Tc-103 12.611 1.182 4.679 0.684 -1.198 7.098 0.692 Tc-102 13.006 0.000 4.218 0.592 -1.461 4.334 0.267 Mo-102 13.056 2.376 4.689 0.670 -0.069 8.293 1.398 Mo-101 14.580 1.194 4.672 0.597 -1.025 6.467 0.984 Mo-100 12.840 2.400 3.838 0.682 0.173 8.102 2.339 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /17/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) K.Shibata, J. Nucl. Sci. Technol., 50, 1177 (2013). 2) H.G.Priesmeyer, H.H.Jung, Atomkernenergie, 19,111 (1972). 3) R.A.Shaw et al., Bull. Amer. Phys. Soc., 20, 560 (1975). 4) R.L.Macklin, J.Halperin, Nucl. Sci. Eng., 73, 174 (1980). 5) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A," Academic Press (1981). 6) P.M.Lantz, ORNL 3679, p.11 (1964). 7) R.E.Heft, 1978 MAYAG, p.495 (1978). 8) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier (2006). 9) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 10) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 11) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 12) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 13) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 14) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 15) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 16) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 17) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).